COLLOQUIUM: Motivations for Spherical Torus research and initial results from NSTX Upgrade
The Spherical Torus/Tokamak (ST) is being explored as a possible means of accelerating the development of magnetic fusion energy. The ST offers access to a higher ratio of plasma pressure to magnetic field pressure and extends toroidal confinement physics understanding including support for ITER burning plasma physics. The ST may also provide an attractive configuration for fusion applications including plasma-material-interface solution development, fusion nuclear component testing, and a net-electricity producing Pilot Plant. The NSTX Upgrade (NSTX-U) facility at PPPL supports all of these research goals and carried out a productive 10 week commissioning and initial research campaign in 2016. ST physics and applications, research highlights from the first NSTX-U campaign, and an overview of NSTX-U longer-term goals will be described.
The Princeton Plasma Physics Laboratory 2019-2020 Colloquium Committee is comprised of the following people. Please feel free to contact them by e-mail regarding any possible speakers or topics for future colloquia.
- Carol Ann Austin 609-243-2484
Princeton Plasma Physics Laboratory is a U.S. Department of Energy national laboratory managed by Princeton University.
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